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JAEA Reports

Manufacture of substitutive assemblies for MONJU reactor decommissioning

Sakakibara, Hiroshi; Aoki, Nobuhiro; Muto, Masahiro; Otabe, Jun; Takahashi, Kenji*; Fujita, Naoyuki*; Hiyama, Kazuhiko*; Suzuki, Hirokazu*; Kamogawa, Toshiyuki*; Yokosuka, Toru*; et al.

JAEA-Technology 2020-020, 73 Pages, 2021/03

JAEA-Technology-2020-020.pdf:8.26MB

The decommissioning is currently in progress at the prototype fast breeder reactor Monju. Fuel assemblies will be taken out of its core for the first step of the great task. Fuel assemblies stand on their own spike plugged into a socket on the core support plate and support with adjacent assemblies through their housing pads each other, resulting in steady core structure. For this reason, some substitutive assemblies are necessary for the purpose of discharging the fuel assemblies of the core. Monju side commissioned, therefore, Plutonium Fuel Development Center to manufacture the substitutive assemblies and the Center accepted it. This report gives descriptions of design, manufacture, and shipment in regard to the substitutive assemblies.

Journal Articles

Accuracy of prediction method of cryogenic tensile strength for austenitic stainless steels in ITER toroidal field coil structure

Sakurai, Takeru; Iguchi, Masahide; Nakahira, Masataka; Saito, Toru*; Morimoto, Masaaki*; Inagaki, Takashi*; Hong, Y.-S.*; Matsui, Kunihiro; Hemmi, Tsutomu; Kajitani, Hideki; et al.

Physics Procedia, 67, p.536 - 542, 2015/07

 Times Cited Count:3 Percentile:73.17(Physics, Applied)

Japan Atomic Energy Agency (JAEA) has developed the tensile strength prediction method at liquid helium temperature (4K) using the quadratic curve as a function of the content of carbon and nitrogen in order to establish the rationalized quality control of the austenitic stainless steel used in the ITER superconducting coil operating at 4K. ITER is under construction aiming to verify technical demonstration of a nuclear fusion generation. Toroidal Field Coil (TFC), one of superconducting system in ITER, have been started procurement of materials in 2012. JAEA is producing materials for actual product which are the forged materials with shape of rectangle, round bar, asymmetry and etc. JAEA has responsibility to procure all ITER TFC Structures. In this process, JAEA obtained many tensile strength of both room temperature and 4K about these structural materials, for example, JJ1: High manganese stainless steel for structure (0.03C-12Cr-12Ni-10Mn-5Mo- 0.24N) and 316LN: High nitrogen containing stainless steel (0.2Nitrogen). Based on these data, accuracy of 4K strength prediction method for actual TFC Structure materials was evaluated and reported in this study.

Journal Articles

Performance upgrade in the JAEA actinide science beamline BL23SU at SPring-8 with a new twin-helical undulator

Saito, Yuji; Fukuda, Yoshihiro; Takeda, Yukiharu; Yamagami, Hiroshi; Takahashi, Sunao*; Asano, Yoshihiro*; Hara, Toru*; Shirasawa, Katsutoshi*; Takeuchi, Masao*; Tanaka, Takashi*; et al.

Journal of Synchrotron Radiation, 19(3), p.388 - 393, 2012/05

 Times Cited Count:102 Percentile:97.1(Instruments & Instrumentation)

The soft X-ray beamline BL23SU at SPring-8 has undergone an upgrade with a twin-helical undulator of in-vacuum type to enhance the experimental capabilities of the end stations. The new light source with a fast helicity-switching operation allows not only the data throughput but also the sensitivity in X-ray magnetic circular dichroism (XMCD) to be improved. The operational performance and potential are described by presenting XMCD results of paramagnetic $$beta$$-US$$_{2}$$ measured with a 10 T superconducting magnet.

Journal Articles

Development of manufacturing technologies for ITER Toroidal Field coil conductors

Hamada, Kazuya; Takahashi, Yoshikazu; Nabara, Yoshihiro; Kawano, Katsumi; Ebisawa, Noboru; Oshikiri, Masayuki; Tsutsumi, Fumiaki; Saito, Toru*; Nakajima, Hideo; Matsuda, Hidemitsu*; et al.

Teion Kogaku, 47(3), p.153 - 159, 2012/03

The Japan Atomic Energy Agency (JAEA) has the responsibility to procure 25% of the ITER Toroidal Field coil conductors as the Japanese Domestic Agency (JADA) in the ITER project. The TF conductor is a circular shaped, cable-in-conduit conductor, composed of a cable and a stainless steel conduit (jacket). The outer diameter and maximum length of the TF conductor are 43.7 mm and 760 m, respectively. JAEA has constructed newly conductor manufacturing facility. Prior to starting conductor, JAEA manufactured a 760-m long Cu dummy conductor as process qualification of dummy cable, the jacket sections and fabrication procedures, such as welding, cable insertion, compaction and spooling. Following qualification of all manufacturing processes, JAEA has started to fabricate superconducting conductors for the TF coils.

Journal Articles

Compact DEMO, SlimCS; Design progress and issues

Tobita, Kenji; Nishio, Satoshi; Enoeda, Mikio; Kawashima, Hisato; Kurita, Genichi; Tanigawa, Hiroyasu; Nakamura, Hirofumi; Honda, Mitsuru; Saito, Ai*; Sato, Satoshi; et al.

Nuclear Fusion, 49(7), p.075029_1 - 075029_10, 2009/07

 Times Cited Count:139 Percentile:97.7(Physics, Fluids & Plasmas)

Recent design study on SlimCS focused mainly on the torus configuration including blanket, divertor, materials and maintenance scheme. For vertical stability of elongated plasma and high beta access, a sector-wide conducting shell is arranged in between replaceable and permanent blanket. The reactor adopts pressurized-water-cooled solid breeding blanket. Compared with the previous advanced concept with supercritical water, the design options satisfying tritium self-sufficiency are relatively scarce. Considered divertor technology and materials, an allowable heat load to the divertor plate should be 8 MW/m$$^{2}$$ or lower, which can be a critical constraint for determining a handling power of DEMO (a combination of alpha heating power and external input power for current drive).

Journal Articles

Soft X-ray absorption magnetic circular dichroism study of ferromagnetic superconductor UGe$$_2$$

Okane, Tetsuo; Okamoto, Jun*; Mamiya, Kazutoshi*; Fujimori, Shinichi; Takeda, Yukiharu; Saito, Yuji; Muramatsu, Yasuji*; Fujimori, Atsushi*; Haga, Yoshinori; Yamamoto, Etsuji; et al.

Journal of the Physical Society of Japan, 75(2), p.024704_1 - 024704_5, 2006/02

 Times Cited Count:12 Percentile:58.23(Physics, Multidisciplinary)

no abstracts in English

Journal Articles

Helicity switching of circularly polarized undulator radiation by local orbit bumps

Hara, Toru*; Shirasawa, Katsutoshi*; Takeuchi, Masao*; Seike, Takamitsu*; Saito, Yuji; Muro, Takayuki*; Kitamura, Hideo*

Nuclear Instruments and Methods in Physics Research A, 498(1-3), p.496 - 502, 2003/02

 Times Cited Count:58 Percentile:95.43(Instruments & Instrumentation)

no abstracts in English

Journal Articles

A Production of non-strain spacing of lattice planes measurement equipment and a measurement of general structure material

Minakawa, Nobuaki; Moriai, Atsushi; Morii, Yukio; Saito, Toru*

Nihon Zairyo Gakkai Dai-37-Kai X Sen Zairyo Kyodo Ni Kansuru Shimpojiumu Koen Rombunshu, p.220 - 222, 2001/00

no abstracts in English

Journal Articles

Development of measurement technique for lattice spacing at stress free by neutron diffraction method

Minakawa, Nobuaki; Saito, Toru; Morii, Yukio; Sasaki, Toshihiko*; Hirose, Yukio*

Nihon Zairyo Gakkai Dai-36-Kai X Sen Zairyo Kyodo Ni Kansuru Shimpojiumu Koen Rombunshu, p.253 - 258, 2000/09

no abstracts in English

Journal Articles

The Residual stress measurement of shot peened IN718 by the neutron diffraction method

Minakawa, Nobuaki; Moriai, Atsushi; Saito, Toru; Tanaka, Keisuke*; Akiniwa, Yoshiaki*; Hayashi, Makoto*; Okido, Shinobu*

Nihon Zairyo Gakkai Dai-36-Kai X Sen Zairyo Kyodo Ni Kansuru Shimpojiumu Koen Rombunshu, p.263 - 265, 2000/09

no abstracts in English

Journal Articles

Evaluation of internal stress using texture

Minakawa, Nobuaki; Morii, Yukio; Saito, Toru*

Proceedings of 6th International Conference on Residual Stressess (ICRS-6), Vol.2, p.1112 - 1115, 2000/07

no abstracts in English

Journal Articles

Neutron diffraction measurement of internal residual stress of superconducting coil jacket

Tsuchiya, Yoshinori; Kikuchi, Kenji; Minakawa, Nobuaki; Morii, Yukio; Kato, Takashi; Nakajima, Hideo; Refal, M.*; Saito, Toru*; Tsuji, Hiroshi

Proceedings of 6th International Conference on Residual Stressess (ICRS-6), Vol.1, p.337 - 341, 2000/00

no abstracts in English

Journal Articles

Characteristics of Li$$_{2}$$O pebbles fabricated by the melting granulation method

*; Kawamura, Hiroshi; Nakamichi, Masaru; Imaizumi, Hideki*; Saito, Minoru; *; Nagakura, Masaaki*

Journal of Nuclear Materials, 219, p.240 - 245, 1995/00

 Times Cited Count:14 Percentile:77.9(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Characteristics of pebble packing and evaluation of sweep gas pressure drop into the in-pile mock-up fusion blanket

Ishitsuka, Etsuo; Nakamichi, Masaru; Kawamura, Hiroshi; Sagawa, Hisashi; *; *; Saito, Minoru

Journal of Nuclear Materials, 212-215, p.881 - 884, 1994/00

 Times Cited Count:2 Percentile:28.05(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Review on JMTR safety design for LEU core conversion

; Miyazawa, Masataka; ; ; *; Yamamoto, Katsumune; Oyamada, Rokuro; Saito, Minoru

JAERI-M 93-227, 73 Pages, 1993/12

JAERI-M-93-227.pdf:2.58MB

no abstracts in English

Journal Articles

Release of short-lived noble gases from HTGR fuel with failed coated fuel particles and contaminated matrix

Ogawa, Toru; Kobayashi, Fumiaki; Tobita, Tsutomu; Fukuda, Kosaku; Saito, Takashi; Yokouchi, Iichiro;

Nucl. Eng. Des., 132, p.31 - 37, 1991/00

 Times Cited Count:10 Percentile:72.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of the SESAME metallic fuel performance code

*; *; *; Ogawa, Toru; *; *; *; Saito, Hioraki*

Nuclear Technology, 89, p.183 - 193, 1990/02

 Times Cited Count:29 Percentile:91.16(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Cross-sectional hydrogen content and mass density profiles of DLC film by neutron and X-ray reflectivity

Ozeki, Kazuhide*; Yonemura, Masao*; Masuzawa, Toru*; Saito, Hidetoshi*; Ogoe, Yasuharu*; Hirakuri, Kenji*; Takeda, Masayasu

no journal, , 

Hydrogen content in the DLC film is very important factor because it greatly influences on its mechanical properties and microstructure such as hardness, wear resistance, surface roughness, and sp3/sp2 ratio. In the present study, we prepared the DLC film using plasma CVD technique varying H$$_{2}$$/CH$$_{4}$$ ratio from 0 to 9. Cross-sectional hydrogen content and mass density profiles of the films were defined by neutron and X-ray reflectivity measurements, and the results were compared with that from ERDA analysis. And O/C atomic ratio of the oxide layer of the film surface was also analyzed using XPS. From the neutron and X-ray reflectivity analysis, hydrogen content and mass density in the DLC film increased with film depth from the surface, and average hydrogen content showed more than 30 % in all films. By combining with XPS results, it is clarified that hydrogen content in the surface layer was lower than that in bulk layer.

Oral presentation

XMCD spectroscopy using a twin helical undulator

Saito, Yuji; Fukuda, Yoshihiro; Takeda, Yukiharu; Hara, Toru*; Shirasawa, Katsutoshi*; Takeuchi, Masao*; Kitamura, Hideo*

no journal, , 

The SPring-8 BL23SU (JAEA Actinide Science beamline) has been upgraded by the replacement of the original APPLE-2 type undulator with a twin helical undulator using in-vacuum devices. Recently, polarization switching between beams of opposite helicity at 1 Hz has reached operational status. The test results clearly show that the new light source is very well suited for the measurement of precision X-ray absorption, magnetic circular dichroism, spectra, as well as element-specifc hysteresis loops.

Oral presentation

Quench test on ITER Nb$$_{3}$$Sn CICC

Suwa, Tomone; Ozeki, Hidemasa; Nabara, Yoshihiro; Saito, Toru*; Kawano, Katsumi; Takahashi, Yoshikazu; Isono, Takaaki; Nunoya, Yoshihiko

no journal, , 

no abstracts in English

21 (Records 1-20 displayed on this page)